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高速炉用群定数セットJFS3-J3Tの作成とZPPR-9の解析

Production of fast reactor group constant set JFS3-J3T and analysis of ZPPR-9

高野 秀機*; 金子 邦男*; 石黒 幸雄*

Takano, Hideki*; Kaneko, Kunio*; Ishiguro, Yukio*

JENDL-3T核データより70群高速炉用炉定数セットJFS-3-J3Tを作成し、1次元ベンチマーク計算及びZPPR-9とFLA-VI-2炉心の解析を行った。その結果は次のように要約される。(1)k$$_{eff}$$はPu炉心で0.6%過小評価、U炉心で2%過大評価(2)中心反応率比は$$sigma$$$$_{f}$$(Pu-239)/$$sigma$$$$_{f}$$(U-235)は実験値との一致がよいが、$$sigma$$$$_{c}$$(U-238)/$$sigma$$$$_{f}$$(Pu-239)と$$sigma$$$$_{f}$$(U-238)/$$sigma$$$$_{f}$$(U-235)は過大評価(3)ドップラー及びNa-ボイド反応度は実験値との一致が良く、JENDL-2の結果を改善している。(4)反応率分布はJENDL-2のC/E-値の半径方向依存性を幾分改善しているが十分ではない。以上の結果を参考に重要接種の接データについて改訂されたJENDL-3T/Rev.1についてもベンチマーク・テストを実施した。JENDL-3T/Rev.1の核特性予測精度はJENDL-2よりも、中心反応率比$$sigma$$$$_{c}$$(U-238)/$$sigma$$$$_{f}$$(Pu-239)と$$sigma$$$$_{f}$$(U-238)/$$sigma$$$$_{f}$$(U-235)の過大評価を除いて優れていた。

The fast reactor 70-group constant set JFS-3-J3T has been generated by using the JENDL-3T nuclear data. One-dimensional benchmark calculations and the analyses of the ZPPR-9 and FCA-VI-2 assemblies were performed with the JFS-3-J3T set. The results obtained are summarized as follows: (1)The k$$_{eff}$$'s are underestimated by 0.6% for Pu-fuel cores and overestimated by 2% for U-fuel cores. (2)The central reaction rate ratio $$sigma$$$$_{f}$$(Pu-239)/$$sigma$$$$_{f}$$(U-235)is in a good agreement with the experimental value and $$sigma$$$$_{c}$$(U-238)/$$sigma$$$$_{f}$$(Pu-239) is overestimated. (3)Doppler and Na-void reactivities are in a good agreement with the measured data. (4)The radial reaction rate distributions are improved in the comparison of the results obtained with the JENDL-2 data. Furthermore, the benchmark test of JENDL-3T/Rev.1 which was revised for several important nuclides on the basis of the results described above has been performed. It was shown that JENDL-3T/Rev.1 predicted nuclear characteristics more satisfactory than JENDL-2, excepting the overestimate for the reaction rate ratios of $$sigma$$$$_{c}$$(U-238)/$$sigma$$$$_{f}$$(Pu-239) and $$sigma$$$$_{f}$$(U-238)/$$sigma$$$$_{f}$$(U-235).

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